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Ceramic Coatings for Nuclear Fuel Cladding to Enhance Accident Tolerance

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자료유형E-Book
개인저자Alat, Ece.
단체저자명The Pennsylvania State University. Materials Science and Engineering.
서명/저자사항Ceramic Coatings for Nuclear Fuel Cladding to Enhance Accident Tolerance.
발행사항[S.l.] : The Pennsylvania State University., 2018
발행사항Ann Arbor : ProQuest Dissertations & Theses, 2018
형태사항235 p.
소장본 주기School code: 0176.
ISBN9780438134409
일반주기 Source: Dissertation Abstracts International, Volume: 79-12(E), Section: B.
요약This research is focused on developing nuclear fuel claddings with ceramic coatings that can perform well during normal operation and can withstand transient conditions such as loss of coolant accident for longer durations than current cladding
요약Zirconium-based alloys are currently widely used as cladding materials due to their low neutron absorption cross-section, good mechanical properties and high melting point. However, waterside corrosion of these alloys cause zirconium oxide forma
요약Cathodic arc physical vapor deposition was used since it provides flexibility in coating properties by adjustment of deposition parameters. A systematic study was performed to identify the optimum deposition parameters to achieve enhanced adhesi
요약Mechanical performance evaluation involved scratch testing and post-scratched sample failure mode characterization. The corrosion tests were performed at Westinghouse in autoclave in static pure water at 360째C and 18.7 MPa up to 128 days in orde
요약The results determined that 8-layer TiN/TiAlN coatings deposited with optimized parameters achieved good adhesion and substantially enhanced corrosion performance, which makes this approach promising for development of accident tolerant nuclear
일반주제명Materials science.
Nuclear engineering.
언어영어
기본자료 저록Dissertation Abstracts International79-12B(E).
Dissertation Abstract International
대출바로가기http://www.riss.kr/pdu/ddodLink.do?id=T15000623

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